A neutron source emissivity setting device and a neutron source emissivity measurement method

CN123010031APending Publication Date: 2026-10-30CHINA INSTITUTE OF ATOMIC ENERGY
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Patent Information

Application Number
CN202610902564.7
Authority / Receiving Office
CN · China
Patent Type
Applications(China)
Current Assignee / Owner
Filing Date
2026-06-22
Publication Date
2026-10-30

AI Technical Summary

Technical Problem

[0002]中子放射源是用于产生中子的装置,在科研、医疗、工业、农业行业中有着广泛的用途,中子发射率是衡量中子放射源强度的核心参数,测量中子发射率通常需要在实验室中进行,但中子放射源具有放射性转移管控严格,不便于运输至实验室进行测量

Benefits of technology

[0016]本申请实施例提供的中子源发射率定值装置和中子源发射率测量方法,通过将中子放射源和探测器先后转移至同一个第二容纳腔内,待中子放射源将中子辐射至活化液之后,将中子放射源移出第二容纳腔,并将探测器转移至第二容纳腔中,以检测活化液衰变放出的γ射线,从而确认中子放射源的中子发射率。如此,无需额外设置测量室,能够简化中子源发射率定值装置的结构,从而减少中子源发射率定值装置的体积,以便于运输。

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Abstract

The embodiment of the present application provides a neutron source emissivity setting device and a neutron source emissivity measuring method. The neutron source emissivity setting device comprises a moving assembly and a detection assembly, and the detection assembly is arranged on the moving assembly. A solution tank has a first accommodating cavity and a second accommodating cavity arranged in a separated mode, and the first accommodating cavity surrounds the second accommodating cavity. The second accommodating cavity is used for accommodating a detector or a neutron radiation source, and the first accommodating cavity is used for accommodating an activation liquid. The activation liquid is used for absorbing radiation of the neutron radiation source, and the detector is used for detecting gamma rays emitted by the decay of the activation liquid. The neutron radiation source is stored in a first storage structure. The detector is stored in a second storage structure. A transfer structure is used for transferring the neutron radiation source from the first storage structure to the second accommodating cavity, and is also used for transferring the detector from the second storage structure to the second accommodating cavity after the neutron radiation source is transferred from the second accommodating cavity to the first storage structure. A measuring chamber is not needed, and the structure of the neutron source emissivity setting device can be simplified.
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Description

Technical Field

[0001] This application relates to the technical field of neutron metrology, and in particular to a neutron source emissivity setting device and a neutron source emissivity measurement method. Background Technology

[0002] A neutron radiation source is a device used to generate neutrons and has a wide range of applications in scientific research, medicine, industry, and agriculture. Neutron emissivity is the core parameter for measuring the intensity of a neutron radiation source. Neutron emissivity measurement usually needs to be carried out in a laboratory, but neutron radiation sources are subject to strict control over radioactive transfer, making it inconvenient to transport them to a laboratory for measurement.

[0003] In related technologies, a portable neutron source emissivity setting device is used to set the neutron emissivity of a neutron radiation source. However, the neutron source emissivity setting device has a complex structure, large size, and is not convenient for transportation. Summary of the Invention

[0004] In view of this, the embodiments of this application aim to provide a neutron source emissivity setting device and a neutron source emissivity measurement method to simplify the structural complexity of the neutron source emissivity setting device.

[0005] This application provides a neutron source emissivity setting device, characterized in that it includes a moving component and a detection component, wherein the detection component is disposed on the moving component; The detection component includes: detector; A solution tank having a first and a second accommodating cavity arranged separately, with the first accommodating cavity surrounding the second accommodating cavity, the second accommodating cavity for accommodating the detector or neutron radiation source, the first accommodating cavity for accommodating an activation liquid for absorbing radiation from the neutron radiation source, and the detector for detecting gamma rays emitted by the decay of the activation liquid. The first storage structure, wherein the neutron radiation source is stored in the first storage structure; The detector is stored in the second storage structure. The transfer structure is used to transfer the neutron radiation source from the first storage structure to the second receiving cavity, and is also used to transfer the detector from the second storage structure to the second receiving cavity after transferring the neutron radiation source from the second receiving cavity to the first storage structure.

[0006] In some embodiments, the detection component includes a guide rail structure supported on the moving component and located above the solution tank, the guide rail structure extending along a first direction, the transfer structure disposed on the guide rail structure and movable relative to the guide rail structure, and the first storage structure and the second storage structure respectively located on both sides of the solution tank along the first direction; Wherein, the first direction is perpendicular to the height direction of the neutron source emission rate setting device.

[0007] In some embodiments, the solution tank has an upward-facing opening that communicates with the second receiving cavity; And / or, the first storage structure has a first channel extending upward and penetrating the upward-facing end face of the first storage structure, and the neutron radiation source is stored in the first storage structure via the first channel; And / or, the second storage structure has a second channel extending upward and penetrating the upward-facing end face of the second storage structure, and the detector is stored in the second storage structure via the second channel.

[0008] In some implementations, the detection component includes a drive motor for driving the transfer structure to move relative to the guide rail structure.

[0009] In some embodiments, the transfer structure includes a body and a clamp, the body being disposed on the guide rail structure and movable relative to the guide rail structure, and the clamp being disposed on the body and movable relative to the body in the height direction.

[0010] In some embodiments, the neutron source emission rate setting device includes a tray structure on which the neutron emission source is supported, the tray structure having a first lifting part, and the clamp being used at least to clamp the first lifting part; And / or, the detector has a second lifting section, and the clamp is at least used to clamp the second lifting section.

[0011] In some implementations, the mobile component includes a mobile chassis and a support structure, the support structure being supported on the mobile chassis, and the support structure and the mobile chassis forming a detection space, in which the detection component is disposed.

[0012] In some embodiments, the detection assembly includes a circulation pipeline and at least two control valves, the circulation pipeline having an inlet and an outlet at both ends, the inlet and the outlet respectively communicating with the first accommodating cavity; At least one of the control valves is used to control the connection or disconnection between the liquid inlet and the first receiving cavity, and at least one of the control valves is used to control the connection or disconnection between the liquid outlet and the first receiving cavity.

[0013] In some embodiments, the detection component includes a circulation pump disposed in the circulation line for driving the flow of liquid in the circulation line.

[0014] In some embodiments, the projection of the second containment cavity onto the vertical plane of the neutron source emission rate setting device at least covers the geometric center of the projection of the solution tank.

[0015] This application embodiment also provides a neutron source emissivity measurement method, characterized in that it is used in the neutron source emissivity setting device described in any of the above embodiments; the neutron source emissivity measurement method includes: The neutron radiation source is removed from the first storage structure and placed into the second containment cavity to irradiate the activation liquid in the first containment cavity; The neutron radiation source is removed from the second receiving cavity and placed into the first storage structure; The activation solution is controlled to circulate along the circulation pipeline to ensure that the ions that capture neutrons are evenly distributed in the activation solution. The detector is removed from the second storage structure and placed into the second containment cavity to measure the gamma rays emitted by the decay of the activation liquid in the first containment cavity; The detector is removed from the second receiving cavity and placed into the second storage structure.

[0016] The neutron source emissivity determination device and neutron source emissivity measurement method provided in this application involve sequentially transferring the neutron radiation source and detector into the same second containment cavity. After the neutron radiation source radiates neutrons into the activation liquid, the neutron radiation source is removed from the second containment cavity, and the detector is transferred into the second containment cavity to detect the gamma rays emitted by the decay of the activation liquid, thereby confirming the neutron emissivity of the neutron radiation source. This eliminates the need for an additional measurement chamber, simplifying the structure of the neutron source emissivity determination device and reducing its size for easier transportation. Attached Figure Description

[0017] Figure 1 This is a schematic diagram of a neutron source emissivity setting device provided in an embodiment of this application; Figure 2 for Figure 1 A schematic diagram of the solution tank in the diagram; Figure 3 for Figure 1 A schematic diagram of the first storage structure in the diagram; Figure 4 for Figure 1 A schematic diagram of the second storage structure in the diagram; Figure 5 This is a schematic diagram illustrating a neutron source emissivity measurement method provided in an embodiment of this application.

[0018] Explanation of reference numerals in the attached figures 1. Neutron source emissivity setting device; 11. First storage structure; 11a. First channel; 111. Tray structure; 12. Second storage structure; 12a. Second channel; 13. Solution tank; 13a. First receiving cavity; 13b. Second receiving cavity; 13c. Opening; 14. Circulation pipeline; 14a. Liquid inlet; 14b. Liquid outlet; 15. Control valve; 16. Circulation pump; 17. Transfer structure; 171. Main body; 172. Clamp; 18. Guide rail structure; 19. Detector; 21. Mobile chassis; 211. Casters; 22. Mobile support; 23. Fixed support. Detailed Implementation

[0019] To make the objectives, technical solutions, and advantages of this application clearer, the following detailed description is provided in conjunction with the accompanying drawings and embodiments. It should be understood that the specific embodiments described herein are merely illustrative and not intended to limit the scope of this application.

[0020] The specific technical features described in the specific embodiments can be combined in any suitable manner without contradiction. For example, different combinations of specific technical features can form different embodiments and technical solutions. To avoid unnecessary repetition, the various possible combinations of the specific technical features in this application will not be described separately.

[0021] In the following description, the terms "first," "second," etc., are used merely to distinguish different objects and do not indicate that the objects have the sameness or relationship. It should be understood that the directional descriptions "above," "below," "outside," and "inside" refer to the orientation under normal use conditions, while "left" and "right" refer to the left and right directions shown in the corresponding diagrams, which may or may not be the left and right directions under normal use conditions.

[0022] It should be noted that the terms "comprising," "including," or any other variations thereof are intended to cover non-exclusive inclusion, such that a process, method, article, or apparatus that comprises a list of elements includes not only those elements but also other elements not expressly listed, or elements inherent to such a process, method, article, or apparatus. Unless otherwise specified, an element defined by the phrase "comprising one..." does not exclude the presence of other identical elements in the process, method, article, or apparatus that includes that element. "A plurality of" means two or more.

[0023] This application provides a neutron source emissivity setting device 1. Please refer to... Figures 1 to 4 The neutron source emission rate setting device 1 includes a moving component and a detection component, with the detection component disposed on the moving component.

[0024] It is understood that the moving component can move the detection component under the action of external force. When the neutron radiation source to be detected is difficult to transport to the laboratory, the neutron source emissivity setting device 1 of this application embodiment can be moved to facilitate transportation to the location of the neutron radiation source for detection of the difficult-to-transport neutron radiation source.

[0025] Please refer to Figures 1 to 4 The detection assembly includes a detector 19, a solution tank 13, a first storage structure 11, a second storage structure 12, and a transfer structure 17. Please refer to... Figure 2 The solution container 13 has a first receiving cavity 13a and a second receiving cavity 13b arranged separately, with the first receiving cavity 13a surrounding the second receiving cavity 13b. The second receiving cavity 13b is used to contain a detector 19 or a neutron radiation source, the first receiving cavity 13a is used to contain an activation liquid, which is used to absorb radiation from the neutron radiation source, and the detector 19 is used to detect gamma rays emitted by the decay of the activation liquid. Please refer to [reference needed]. Figure 3 The neutron radiation source is stored in the first storage structure 11. Please refer to... Figure 4 The detector 19 is stored in the second storage structure 12. The transfer structure 17 is used to transfer the neutron radiation source from the first storage structure 11 to the second receiving cavity 13b, and also to transfer the detector 19 from the second storage structure 12 to the second receiving cavity 13b after the neutron radiation source is transferred from the second receiving cavity 13b to the first storage structure 11.

[0026] Understandably, the first storage structure 11 can provide storage space for the neutron radiation source. When the neutron radiation source is not transferred to the second receiving cavity 13b or after the neutron radiation source is removed from the second receiving cavity 13b, it can be stored in the first storage structure 11, which can reduce the time the neutron radiation source is exposed to the outside, so as to ensure the safety of the neutron radiation source.

[0027] Understandably, the second storage structure 12 can provide storage space for the detector 19. When the detector 19 is not transferred to the second receiving cavity 13b or after the detector 19 is removed from the second receiving cavity 13b, it can be stored in the second storage structure 12, which can reduce the possibility of the detector 19 being irradiated by the neutron radiation source, so as to ensure the safety of the detector 19.

[0028] It should be noted that the specific type of activation solution is not limited; for example, the activation solution can be an aqueous solution of manganese sulfate or an aqueous solution of vanadium sulfate.

[0029] It should be noted that the specific type of detector 19 is not limited; for example, detector 19 may be a sodium iodide detector or a lanthanum bromide detector.

[0030] Understandably, the first cavity 13a and the second cavity 13b are not connected to each other, and the activation liquid in the first cavity 13a will not enter the second cavity 13b. When the neutron radiation source is transferred to the second cavity 13b, the activation liquid will not come into direct contact with the neutron radiation source, which can reduce the possibility of the activation liquid corroding the neutron radiation source. In addition, the first cavity 13a surrounds the second cavity 13b. The neutrons emitted by the neutron radiation source transferred to the second cavity 13b will be captured by the activation liquid in the first cavity 13a. Similarly, the detector 19 transferred to the second cavity 13b can detect the intensity of the gamma rays emitted by the decay of the activation liquid after the neutrons are captured in the first cavity 13a, thereby confirming the neutron emissivity of the neutron radiation source.

[0031] For example, the principle of the neutron source emissivity setting device 1 for detecting neutron emissivity is as follows: when the neutron radiation source is transferred to the second receiving cavity 13b, the neutrons emitted by the neutron radiation source will be captured by 55Mn in the manganese sulfate aqueous solution to produce 56Mn with a half-life of 2.578h. After β decay, 56Mn becomes 56Fe. During the decay process, 56Mn will release γ rays. By detecting γ rays, the amount of 56Mn in the saturated activated manganese sulfate aqueous solution can be calculated, thereby the neutron emissivity of the neutron radiation source can be calculated.

[0032] Understandably, detector 19 is able to detect the gamma rays released by 56Mn in the activating solution during its decay process.

[0033] Understandably, the transfer structure 17 can transfer the neutron radiation source and detector 19 without requiring close manual operation by the operator, thereby reducing the possibility of the operator being exposed to the radiation range of the neutron radiation source and ensuring the safety of the operator.

[0034] Furthermore, compared to the technical solution of operators manually transferring the neutron radiation source and detector 19 at close range, the transfer structure 17 makes it easier to locate the neutron radiation source and detector 19 to the second receiving cavity 13b, thereby improving the positioning accuracy of the transferred neutron radiation source and detector 19 and ensuring the accuracy of the detection results of the neutron source emissivity setting device 1.

[0035] In related technologies, the neutron radiation source is placed inside the solution tank 13, and the detector 19 is placed inside the measurement chamber. The activation liquid irradiated by the neutron radiation source flows through the measurement chamber for detection by the detector 19. The measurement chamber and the solution tank 13 are two independent components and need to be set up separately, which makes the structure of the neutron source emissivity setting device 1 complex, occupies a large space, and is inconvenient to transport.

[0036] The neutron source emissivity determination device 1 provided in this embodiment of the application determines the neutron emissivity by sequentially transferring the neutron radiation source and detector 19 into the same second receiving cavity 13b. After the neutron radiation source radiates neutrons into the activation liquid, the neutron radiation source is removed from the second receiving cavity 13b, and the detector 19 is transferred into the second receiving cavity 13b to detect the intensity of gamma rays emitted by the decay of the activation liquid, thereby confirming the neutron emissivity of the neutron radiation source. This eliminates the need for an additional measurement chamber, simplifying the structure of the neutron source emissivity determination device 1 and reducing its volume for easier transportation.

[0037] In some embodiments, please refer to Figure 1 The detection assembly includes a circulation pipeline 14 and at least two control valves 15. The circulation pipeline 14 has an inlet 14a and an outlet 14b at both ends, which are respectively connected to a first receiving cavity 13a. At least one control valve 15 is used to control the connection or disconnection between the inlet 14a and the first receiving cavity 13a, and at least one control valve 15 is used to control the connection or disconnection between the outlet 14b and the first receiving cavity 13a.

[0038] Understandably, when all control valves 15 are in the open state, the activating liquid in the first receiving cavity 13a can flow into the circulation pipe 14 through the inlet 14a and then flow back into the first receiving cavity 13a through the outlet 14b. Of course, it can also flow into the circulation pipe 14 through the outlet 14b and then flow back into the first receiving cavity 13a through the inlet 14a; this application does not impose any limitation here. In this way, the activating liquid in the first receiving cavity 13a can circulate through the circulation pipe 14, which can agitate the activating liquid in the first receiving cavity 13a, which is beneficial to the uniform distribution of neutron-capturing ions in the activating liquid and can ensure the accuracy of the detection results of the detector 19.

[0039] It should be noted that in this application, "at least two" refers to two or more, and "at least one" refers to one or more.

[0040] It should be noted that the specific power source for the activation liquid in the first receiving cavity 13a to circulate in the circulation pipeline 14 is not limited.

[0041] In some embodiments, please refer to Figure 1 The detection assembly includes a circulation pump 16, which is disposed in the circulation pipeline 14 and is used to drive the liquid flow in the circulation pipeline 14. It is understood that the circulation pump 16 can provide power for the flow of the activation liquid in the circulation pipeline 14, agitate the activation liquid in the first receiving cavity 13a, and make the ions that capture neutrons evenly distributed in the activation liquid, thereby ensuring the accuracy of the detection results of the detector 19.

[0042] It should be noted that the specific type of circulating pump 16 is not limited. For example, circulating pump 16 can be a centrifugal pump, gear pump, peristaltic pump, or vacuum pump, etc.

[0043] In some embodiments, please refer to Figure 1 The detection component includes a guide rail structure 18, which is supported on the moving component and located above the solution tank 13. The guide rail structure 18 extends along a first direction. A transfer structure 17 is disposed on the guide rail structure 18 and is movable relative to the guide rail structure 18. A first storage structure 11 and a second storage structure 12 are respectively located on both sides of the solution tank 13 along the first direction.

[0044] Understandably, the guide rail structure 18 extends along the first direction, enabling the transfer structure 17 to move along the first direction, facilitating the transfer of the neutron radiation source and detector 19 along the first direction. Furthermore, the first storage structure 11 and the second storage structure 12 are arranged along the first direction on both sides of the solution tank 13, also facilitating the transfer of the neutron radiation source and detector 19 by the transfer structure 17, thereby improving the transfer efficiency of the transfer structure 17.

[0045] It should be noted that, please refer to Figure 1 The first direction is perpendicular to the height direction of the neutron source emissivity setting device 1. The first direction refers to... Figure 1 The direction indicated by the arrow in the first direction can be the direction in which the moving component travels.

[0046] It should be noted that the specific manner in which the drive transfer structure 17 moves relative to the guide rail structure 18 is not limited.

[0047] In some embodiments, please refer to Figure 1The detection component includes a drive motor, which drives the transfer structure 17 to move relative to the guide rail structure 18. It is understood that driving the transfer structure 17 to move via the drive motor improves the stability of the movement of the transfer structure 17 relative to the guide rail structure 18, and enhances the reliability of the transfer structure 17 in transferring the neutron radiation source and detector 19.

[0048] It should be noted that there are no restrictions on the specific type of drive motor.

[0049] It should be noted that the specific shape of the solution tank 13 is not limited. For example, the solution tank 13 can be a spherical tank or a column tank.

[0050] In some embodiments, please refer to Figure 1 and Figure 2 The solution container 13 has an upward-facing opening 13c that connects to the second receiving cavity 13b. It is understood that the transfer structure 17 can transfer the neutron radiation source and detector 19 into the second receiving cavity 13b through the opening 13c. The opening 13c faces upwards from the guide rail structure 18, facilitating the extension of the transfer structure 17, which is located on the guide rail structure 18, into the opening 13c, thereby improving the transfer efficiency of the transfer structure 17.

[0051] In some embodiments, please refer to Figure 1 and Figure 2 In the orthographic projection of the vertical plane of the neutron source emission rate setting device 1, the projection of the second containment cavity 13b at least covers the geometric center of the projection of the solution tank 13. Thus, when the neutron radiation source is transferred into the second containment cavity 13b, it is beneficial that the neutrons emitted by the neutron radiation source cover the entire solution tank 13, allowing the activation liquid in the first containment cavity 13a to fully capture neutrons, further improving the accuracy of the detection results of the detector 19.

[0052] It should be noted that the geometric center of the projection of solution tank 13 refers to the geometric center of the shape enclosed by the outer contour of the projection of solution tank 13.

[0053] It should be noted that the specific structure of the first storage structure 11 is not limited.

[0054] For example, please refer to Figure 1 and Figure 3The first storage structure 11 has a first channel 11a, which extends upward and penetrates the upward-facing end face of the first storage structure 11. A neutron emission source is stored in the first storage structure 11 via the first channel 11a. It is understood that the transfer structure 17 can store the neutron emission source in the first storage structure 11 via the first channel 11a, and can also retrieve the neutron emission source from the first storage structure 11 via the first channel 11a. The first channel 11a penetrates the upward-facing end face of the first storage structure 11, facilitating the extension of the transfer structure 17 into the first channel 11a and improving the transfer efficiency of the transfer structure 17.

[0055] For example, the first storage structure 11 is made of a shielding material. This reduces the possibility of radiation leakage from the neutron radiation source stored in the first storage structure 11.

[0056] For example, please refer to Figure 1 and Figure 4 The second storage structure 12 has a second channel 12a extending upwards and penetrating the upward-facing end face of the second storage structure 12. The detector 19 is stored in the second storage structure 12 via the second channel 12a. It is understood that the transfer structure 17 can store the detector 19 in the second storage structure 12 via the second channel 12a, and can also remove the detector 19 from the second storage structure 12 via the first channel 11a. The second channel 12a penetrates the upward-facing end face of the second storage structure 12, facilitating the extension of the transfer structure 17 into the second channel 12a, thereby improving the transfer efficiency of the transfer structure 17.

[0057] For example, the second storage structure 12 is made of a shielding material. In this way, the possibility of radiation exposure to the detector 19 stored in the second storage structure 12 can be reduced.

[0058] It should be noted that the specific structure of transfer structure 17 is not limited.

[0059] In some embodiments, please refer to Figure 1 The transfer structure 17 includes a main body 171 and a clamp 172. The main body 171 is disposed on the guide rail structure 18 and can move relative to the guide rail structure 18. The clamp 172 is disposed on the main body 171 and can move relative to the main body 171 in the height direction.

[0060] It is understandable that the movement of the main body 171 relative to the guide rail structure 18 can adjust the position of the clamp 172 in the first direction, and the movement of the clamp 172 relative to the main body 171 can adjust the position of the clamp 172 in the height direction, thereby increasing the range of motion of the clamp 172. For example, when the main body 171 moves relative to the guide rail structure 18 to above the first storage structure 11, the clamp 172 moves relative to the main body 171 to clamp the neutron radiation source stored in the first storage structure 11. When the main body 171 moves to above the solution tank 13, the clamp 172 then places the clamped neutron radiation source into the second receiving cavity 13b, thereby transferring the neutron radiation source from the first storage structure 11 to the second receiving cavity 13b.

[0061] It should be noted that the specific type of clamp 172 is not limited. For example, clamp 172 can be a split gripper.

[0062] It should be noted that, in the embodiment of the drive motor, the drive motor is used not only to drive the main body 171 to move relative to the guide rail structure 18, but also to drive the clamp 172 to move relative to the main body 171.

[0063] In some embodiments, please refer to Figure 1 and Figure 3 The neutron source emission rate setting device 1 includes a tray structure 111, on which a neutron radiation source is supported. The tray structure 111 has a first lifting part, and a clamp 172 is used to clamp at least the first lifting part.

[0064] Understandably, the neutron radiation source is placed in the tray structure 111, and the neutron radiation source is transferred through the transfer tray structure 111. The clamp 172 does not directly contact the neutron radiation source, which ensures the operational stability of the clamp 172. In addition, the first lifting part also facilitates the clamp 172 to grip, which is beneficial for the transfer structure 17 to transfer the tray structure 111, thereby improving the transfer efficiency of the transfer structure 17.

[0065] It should be noted that the specific shape of the pallet structure 111 is not limited. For example, the shape of the pallet structure 111 can be funnel-shaped or cylindrical, etc.

[0066] For example, the detector 19 has a second lifting section, and the clamp 172 is used to clamp the second lifting section at least. It is understood that the second lifting section facilitates the clamp 172 in clamping, which is beneficial for the transfer structure 17 to transfer the detector 19 and can improve the transfer efficiency of the transfer structure 17.

[0067] It should be noted that the specific structure of the mobile component is not limited.

[0068] In some embodiments, please refer to Figure 1The mobile component includes a mobile chassis 21 and a support structure. The support structure is supported on the mobile chassis 21, and the support structure and the mobile chassis 21 together form a detection space. The detection component is set in the detection space.

[0069] Understandably, the support structure has a certain structural strength, which can protect the detection components and ensure their safety during the transportation of the neutron source emission rate setting device 1.

[0070] It should be noted that the specific configuration of the detection component and the moving component is not limited. For example, the detection component can be detachably disposed within the detection space. Exemplarily, the moving component includes multiple fixed supports 23, all of which are supported by the moving chassis 21 and located within the detection space. Each component in the detection component is supported on the fixed supports 23. In this way, the first storage structure 11 can be detached and transported to the hot chamber, where the neutron radiation source is stored in the first storage structure 11.

[0071] It should be noted that the specific movement method of the mobile chassis 21 is not limited. For example, the mobile chassis 21 includes multiple casters 211, enabling the mobile chassis 21 itself to move. The specific type of casters 211 is not limited; for example, casters 211 can be swivel wheels, which can improve the flexibility of the mobile chassis 21.

[0072] One embodiment of this application provides a neutron source emissivity measurement method, which is used in the neutron source emissivity setting device 1 of any embodiment of this application.

[0073] Please refer to Figure 5 Methods for measuring the emissivity of neutron sources include: S10. The neutron radiation source is removed from the first storage structure 11 and placed into the second receiving cavity 13b.

[0074] Understandably, the neutron radiation source in the second containment cavity 13b can irradiate the activation liquid in the first containment cavity 13a. The neutron radiation source enters the second containment cavity 13b through the opening 13c and can be placed in the second containment cavity 13b near the geometric center of the solution tank 13, so that the distance from the neutron radiation source to the boundaries of the solution tank 13 in all directions is as consistent as possible, so that the neutrons radiated by the neutron radiation source can be more fully captured by the activation liquid in the first containment cavity 13a.

[0075] S20. The neutron radiation source is removed from the second receiving cavity 13b and placed into the first storage structure 11.

[0076] It should be noted that the duration of continuous irradiation by the neutron radiation source in the second containment cavity 13b is unlimited.

[0077] For example, the activation solution is a manganese sulfate solution, and the neutron radiation source continuously irradiates the second containment cavity 13b for more than or equal to 30 hours, so that the activation solution is close to the radioactive equilibrium state, thereby ensuring the accuracy of the neutron source emissivity measurement results.

[0078] S30. Control the activation solution to circulate along the circulation pipeline 14 so that the captured neutron ions are evenly distributed in the activation solution.

[0079] Specifically, all control valves 15 are opened and the circulation pump 16 is run so that the activated liquid in the first containment chamber 13a is circulated through the circulation pipeline 14. After the activated liquid is circulated, it can agitate the activated liquid in the first containment chamber 13a, so that the ions that capture neutrons are evenly distributed in the activated liquid.

[0080] S40. Remove detector 19 from second storage structure 12 and place it into second containment cavity 13b to measure γ-rays emitted by the decay of activation liquid in first containment cavity 13a.

[0081] Thus, detector 19 can measure the activation liquid within the entire first containment cavity 13a, facilitating the reception of γ-rays emitted by the decay of ions that capture neutrons in the activation liquid, and the ray signal received by detector 19 is stable.

[0082] S50, The detector 19 is removed from the second receiving cavity 13b and placed into the second storage structure 12. In this way, the detector 19 can be stored in the second storage structure 12, which can reduce the possibility of the detector 19 being damaged by collision.

[0083] In the description of this application, the terms "one embodiment," "some embodiments," "example," "specific example," or "some examples," etc., refer to specific features, structures, materials, or characteristics described in connection with that embodiment or example, which are included in at least one embodiment or example of the embodiments of this application. In this application, the illustrative expressions of the above terms do not necessarily refer to the same embodiment or example. Moreover, the specific features, structures, materials, or characteristics described may be combined in any suitable manner in one or more embodiments or examples. Furthermore, without contradiction, those skilled in the art can combine different embodiments or examples described in this application, as well as features of different embodiments or examples.

[0084] The above description is merely a preferred embodiment of this application and is not intended to limit the application. Various modifications and variations can be made to this application by those skilled in the art. Any modifications, equivalent substitutions, improvements, etc., made within the spirit and principles of this application should be included within the scope of protection of this application.

Claims

1. A neutron source emittance setting device, characterized in that, It includes a moving component and a detection component, wherein the detection component is disposed on the moving component; The detection component includes: detector; A solution tank having a first and a second accommodating cavity arranged separately, with the first accommodating cavity surrounding the second accommodating cavity, the second accommodating cavity for accommodating the detector or neutron radiation source, the first accommodating cavity for accommodating an activation liquid for absorbing radiation from the neutron radiation source, and the detector for detecting gamma rays emitted by the decay of the activation liquid. The first storage structure, wherein the neutron radiation source is stored in the first storage structure; The detector is stored in the second storage structure. The transfer structure is used to transfer the neutron radiation source from the first storage structure to the second receiving cavity, and is also used to transfer the detector from the second storage structure to the second receiving cavity after transferring the neutron radiation source from the second receiving cavity to the first storage structure.

2. The neutron source emission rate setting device according to claim 1, characterized in that, The detection component includes a guide rail structure, which is supported on the moving component and located above the solution tank. The guide rail structure extends along a first direction. The transfer structure is disposed on the guide rail structure and is movable relative to the guide rail structure. The first storage structure and the second storage structure are respectively located on both sides of the solution tank along the first direction. Wherein, the first direction is perpendicular to the height direction of the neutron source emission rate setting device.

3. The neutron source emission rate setting device according to claim 2, characterized in that, The solution container has an upward-facing opening that communicates with the second receiving cavity; And / or, the first storage structure has a first channel extending upward and penetrating the upward-facing end face of the first storage structure, and the neutron radiation source is stored in the first storage structure via the first channel; And / or, the second storage structure has a second channel extending upward and penetrating the upward-facing end face of the second storage structure, and the detector is stored in the second storage structure via the second channel.

4. The neutron source emission rate setting device according to claim 2, characterized in that, The detection component includes a drive motor, which is used to drive the transfer structure to move relative to the guide rail structure.

5. The neutron source emission rate setting device according to claim 2, characterized in that, The transfer structure includes a main body and a clamp. The main body is disposed on the guide rail structure and is movable relative to the guide rail structure. The clamp is disposed on the main body and is movable relative to the main body in the height direction.

6. The neutron source emission rate setting device according to claim 5, characterized in that, The neutron source emission rate setting device includes a tray structure, the neutron emission source is supported on the tray structure, the tray structure has a first lifting part, and the clamp is used to clamp at least the first lifting part; And / or, the detector has a second lifting section, and the clamp is at least used to clamp the second lifting section.

7. The neutron source emission rate setting device according to any one of claims 1 to 6, characterized in that, The mobile component includes a mobile chassis and a support structure. The support structure is supported on the mobile chassis, and the support structure and the mobile chassis together form a detection space. The detection component is disposed in the detection space.

8. The neutron source emission rate setting device according to any one of claims 1 to 6, characterized in that, The detection assembly includes a circulation pipeline and at least two control valves. The circulation pipeline has an inlet and an outlet at both ends, and the inlet and outlet are respectively connected to the first accommodating cavity. At least one of the control valves is used to control the connection or disconnection between the liquid inlet and the first receiving cavity, and at least one of the control valves is used to control the connection or disconnection between the liquid outlet and the first receiving cavity.

9. The neutron source emission rate setting device according to claim 8, characterized in that, The detection component includes a circulation pump, which is disposed in the circulation pipeline and is used to drive the flow of liquid in the circulation pipeline.

10. The neutron source emission rate setting device according to any one of claims 1 to 6, characterized in that, In the orthographic projection of the vertical plane of the neutron source emission rate setting device, the projection of the second receiving cavity at least covers the geometric center of the projection of the solution tank.

11. A method for measuring the emissivity of a neutron source, characterized in that, The neutron source emissivity determination device according to any one of claims 1-10; the neutron source emissivity measurement method includes: The neutron radiation source is removed from the first storage structure and placed into the second containment cavity to irradiate the activation liquid in the first containment cavity; The neutron radiation source is removed from the second receiving cavity and placed into the first storage structure; The activation solution is controlled to circulate along the circulation pipeline to ensure that the ions that capture neutrons are evenly distributed in the activation solution. The detector is removed from the second storage structure and placed into the second containment cavity to measure the gamma rays emitted by the decay of the activation liquid in the first containment cavity; The detector is removed from the second receiving cavity and placed into the second storage structure.